Kobe Steel, Ltd.

Sumitomo Metal Industries, Inc.

Doryokuro Kakunenryo Kaihatsu Jigyodan

The United States of America As Represented by the United States

Shigeo Nomura

Masayuki Fujiwara

Hiroshi Teranishi

Susumu Hirano

Toshio Nishida

Itaru Shibahara

Takanari Okuda

Kenny C Gross

John D Lambert

Yuji Enokido

Aturou Iseda

Yoshinori Tateishi

Motoharu Nakajima

A dispersion strenghened ferritic steel having excellent ductility and toughness which has been heat treated to produce a matrix having a tempered martensitic structure composed of 0.05 to 0.25% by weight of carbon, 0.1% by weight or less of silicon , 0.1% by weight or less of manganese, 8 to 12% by weight of chromium, 0.1 to 4.0% by weight in total of molybdenum and tungsten, and 0.02% by weight or less of oxygen (exclusive of oxide particles) with the balance being iron and inevitable impurities and, homogeneously dispersed in the matrix, composite oxide particles comprising Y.sub.2 O.sub.3 and TiO.sub.2 in an amount of 0.1 to 1.0% by weight in total of Y.sub.2 O.sub.3 and TiO.sub.2 and a TiO.sub.2 to Y.sub.2 O.sub.3 molar ratio of 0.5 to 2.0.

Dispersion strengthened ferritic steel for high temperature structural

A dispersion strengthened ferritic steel cladding tube for use in a nuclear reactor and having a double-layer structure is provided. The cladding tube comprises a tube body made of a dispersion strengthened ferritic steel having a ceramic dispersed therein and containing 8 to 13% by weight of chromium. The inner surface of the tube body is lined with a ferritic steel containing 18 to 30% by weight of chromium. The cladding tube has not only excellent compatibility with a mixed oxide fuel but also excellent high temperature strength and swelling resistance. A method of producing the cladding tube using powder metallurgy is also provided.

Dispersion strengthened ferritic steel cladding tube for nuclear reactor

The invention provides an apparatus and method for diagnosing breached fuel elements in a nuclear reactor. A detection system measures the activity of isotopes from the cover-gas in the reactor. A data acquisition and processing system monitors the detection system and corrects for the effects of the cover-gas clean up system on the measured activity and further calculates the derivative cure of the corrected activity as a function of time. A plotting system graphs the derivative curve, which represents the instantaneous release rate of fission gas from a breached fuel element.

Method and apparatus for diagnosing breached fuel elements

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Mito, Japan

Shigeo Nomura